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MONTHYEARML0419501012004-07-13013 July 2004 Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call Project stage: Draft RAI ML0421804642004-08-0505 August 2004 RAI, Request to Use a Risk-Informed Inservice Inspection Plan Project stage: RAI ML0424502302004-09-0101 September 2004 Teleconference with PSEG Nuclear, LLC Regarding Hope Creek Generating Station Proposed Implementation of a Risk-Informed Inservice Inspection Plan TAC No. MC2221) Project stage: Meeting ML0430801612004-12-0808 December 2004 Implementation of a Risk-Informed Inservice Inspection Program Project stage: Other 2004-07-13
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Category:Memoranda
MONTHYEARML18269A2522018-10-12012 October 2018 F&O Closure Observation Hope Creek Fire PRA ML17023A1452017-01-23023 January 2017 Summary of Teleconference with PSEG Regarding Hope Creek HPCI ML16259A2042016-09-20020 September 2016 Hope Creek Generating Station - Safety Evaluation - Request to revise technical specifications - safety limit minimum critical power ratio.(TAC NO. MF7793) ML15015A6772015-01-16016 January 2015 Forthcoming Closed Meeting with PSEG Nuclear, LLC, Regarding a Planned Digital Instrumentation and Controls License Amendment Request Associated with Hope Creek Generating Station, Unit 1 IR 05000272/20132022013-12-20020 December 2013 IR 05000272-13-202, 05000311-13-202 & 05000354-13-201, September 9-13, 2013, Salem Nuclear Generating Station and Hope Creek Generating Station - Cover Letter ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13233A1132013-08-22022 August 2013 Notice of Forthcoming Meeting with PSEG Nuclear, LLC Regarding a Planned Digital Instrumentation and Controls License Amendment Request Associated with Hope Creek Generating Station, Unit 1 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML13196A2202012-06-0606 June 2012 Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML1129901422011-10-25025 October 2011 Draft Request for Additional Information ML1129700652011-10-21021 October 2011 Summary of PSEG Drop-in Visit, 9-28-2011 and Slides ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML1118605722011-07-0505 July 2011 Draft Request for Additional Information ML11181A1772011-06-30030 June 2011 June 29, 2011 Summary of Public Meeting to Discuss Observations and Lessons Learned During the Hope Creek Nuclear Generating Station Application of the Nuclear Energy Institute'S Nuclear Safety Culture Assessment Process ML11137A0762011-06-0202 June 2011 Summary of Telephone Conference Call Held on May 11, 2011, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning the Hope Creek License Condition for the Drywell ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML11105A0372011-05-0404 May 2011 Summary of Telephone Conference Call Held on March 25, 2011, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning Findings on the Hope Creek Generating Station Gas Turbine ML1111108862011-04-20020 April 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information LR-N11-0087, 2011 Annual Report - Guarantees of Payment of Deferred Premiums2011-03-31031 March 2011 2011 Annual Report - Guarantees of Payment of Deferred Premiums ML1106801152011-03-0808 March 2011 Draft Request for Additional Information ML1106005572011-03-0101 March 2011 Minutes of the Meeting of the Subcommittee on Plant License Renewal Regarding Hope Creek Generating Plant on November 3, 2010, in Rockville, Maryland ML1034909292011-02-0909 February 2011 Summary of Telephone Conference Call Held on November 18, 2010, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning Findings on the Hope Creek Generating Station Recent Outage ML1101901352011-01-18018 January 2011 Draft Request for Additional Information ML1029500062010-10-28028 October 2010 11/17/10 Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Hope Creek Generating Station and Salem Nuclear Generating Station Units 1 and 2 ML1027100672010-09-30030 September 2010 Advisory Committee on Reactor Safeguards Review of the Hope Creek Generating Station License Renewal Application - Safety Evaluation Report with Open Items ML1027207232010-09-29029 September 2010 Federal Register Notice Regarding the ACRS Subcommittee Meeting on Plant License Renewal (Hope Creek), November 3, 2010 ML1024407062010-09-20020 September 2010 Summary of Telephone Conference Call Held on August 18,2010 Between Us NRC and PSEG Nuclear, LLC Concerning Questions Pertaining to the Hope Creek Generating Station License Renewal Application ML11263A0282010-09-16016 September 2010 E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal Memo ML11263A0272010-09-14014 September 2010 E-mail with Attachment from T. Ghosh, RES, to L. Perkins, NRR Et Al, on Fyi Salem SAMA Transmittal ML1023201782010-09-0303 September 2010 Summary of Telephone Conference Call Held on 8/16/10, Between Us NRC and PSEG Nuclear,Llc,Concerning Draft Request for Additional Information Pertaining to the Hope Creek Generating Station, License Renewal Application ML1023201792010-09-0202 September 2010 Summary of Telephone Conference Call Held on 6/21/10 Between the USNRC and PSEG Nuclear LLC Concerning Responses to Requests for Additional Information Pertaining to the Hope Creek Generating Station License Renewal Application ML1022204762010-08-18018 August 2010 Summary of Telephone Conference Call Held on 8/4/10,Between Us NRC and PSEG Nuclear, LLC, Concerning Draft RAI Pertaining to the Hope Creek Generating Station, License Renewal Application ML1022200122010-08-13013 August 2010 Summary of Telephone Conf Call Held on 7/29/10, Between the USNRC and PSEG Nuclear LLC, Concerning Follow-Up Questions Pertaining to the Salem Nuclear Generating Station, Units 1 & 2, and Hope Creek Generating Station License Renewal Enviro ML1020105012010-07-20020 July 2010 Draft Request for Additional Information ML1018303472010-07-0202 July 2010 Draft Request for Additional Information ML1017600102010-06-24024 June 2010 Draft Request for Additional Information ML1011004322010-04-19019 April 2010 PSEG Slides for Salem and Hope Creek Annual Assessment Meeting, April 6, 2010 ML1009904032010-04-0808 April 2010 Draft Request for Additional Information LR-N10-0115, Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums2010-04-0101 April 2010 Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums ML11259A2702010-03-0101 March 2010 E-mail with Attachment from D. Logan, NRR, to S. Duda, Aecom Et Al, on Mitigation Memo ML1002907322010-01-28028 January 2010 Draft Request for Additional Information ML0934405582009-12-10010 December 2009 Notice of Closed Meeting with PSEG Nuclear LLC (PSEG) to Discuss Exemption from Schedular Requirements of 10 CFR 73.55 for Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 ML0928706352009-10-23023 October 2009 11/05/2009 Notice of Meeting to Discuss License Renewal Process and Environmental Scoping for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station, License Renewal Application Review ML0923606212009-08-27027 August 2009 Logistics Trip Report to Delaware Emergency Management Agency Regarding Salem-Hope Creek License Renewal ML0920103212009-07-30030 July 2009 Logistics Trip Report to Salem and Hope Creek Nuclear Stations and Salem, New Jersey ML0919504062009-07-14014 July 2009 Draft Request for Additional Information ML0917302782009-06-22022 June 2009 PSEG Drop-in Visit (Salem and Hope Creek) on 6-18-2009 ML0913502412009-05-14014 May 2009 Draft Request for Additional Information ML0911701652009-04-27027 April 2009 Draft Request for Additional Information 2018-10-12
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22006A3212022-01-0606 January 2022 NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML21300A0222021-10-27027 October 2021 Notification of Conduct of a Fire Protection Team Inspection ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) ML20295A4922020-10-21021 October 2020 NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131) ML18263A1442018-09-12012 September 2018 NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18150A6912018-05-30030 May 2018 NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542 ML18120A2482018-04-27027 April 2018 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000354/2018403 ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17348A9972017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A6242017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate ML17348A6282017-11-21021 November 2017 NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls ML17320A2152017-11-16016 November 2017 NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002) ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb ML17222A1652017-08-10010 August 2017 NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502) ML17181A1352017-06-29029 June 2017 NRR E-mail Capture - Request for Additional Information Related to Hope Creek and Salem Emergency Action Level Scheme Change License Amendment Request (MF9268/69/70) ML17164A4062017-06-13013 June 2017 NRR E-mail Capture - Hope Creek - Final Request for Additional Information Concerning ILRT (MF8462) ML17027A3282017-02-27027 February 2017 Request for Additional Information Regarding License Amendment Request to Permanently Extend Type a and Type C Leak Rate Test Frequencies ML16321A4642016-11-21021 November 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements ML16277A5142016-11-0303 November 2016 Request for Additional Information Regarding License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16271A2052016-11-0202 November 2016 Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML16231A4272016-08-24024 August 2016 Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16217A4302016-08-17017 August 2016 Request for Additional Information Regarding Digital Power Range Neutron Monitoring System Upgrade ML16007A1742016-05-31031 May 2016 Request for Additional Information Regarding Review of Post-EPU Steam Dryer Stress Calculation Acoustic Circuit Model Software Error ML16089A0792016-05-0505 May 2016 Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16124A5802016-05-0303 May 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes ML15055A3772015-03-10010 March 2015 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57 ML14197A6192014-07-24024 July 2014 and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386) ML14168A2352014-07-0202 July 2014 Request for Additional Information Regarding Flooding Hazard Reevaluation ML13309B5922013-11-22022 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13168A2762013-08-12012 August 2013 Peach Bottom, Units 2 and 3, Request for Additional Information Decommissioning Funding Status Report (TAC No. MF2202; MF2227; MF2228) ML13193A2912013-07-22022 July 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) TAC MF1031 ML13204A2532013-07-19019 July 2013 Draft RAIs - Decommissioning Funding Status Report for Hope Creek and Peach Bottom ML13190A2212013-07-0202 July 2013 RAIs for Hope Creek Regarding Response to Order EA-12-051 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML12334A3102012-12-0505 December 2012 Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items ML12310A1672012-11-0101 November 2012 Draft RAI to License Amendment Request Regarding Average Power Range Monitoring Operability Requirements in Operational Condition 5 ML1227901012012-10-0505 October 2012 Clarifying Information for Question No. 4 (with Attachment) ML12212A1032012-08-0808 August 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information ML12216A1792012-08-0303 August 2012 Draft RAI Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML12213A6162012-07-30030 July 2012 Draft Request for Additional Information Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic 2022-01-06
[Table view] |
Text
July 13, 2004 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Daniel S. Collins, Senior Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC2221)
The attached draft RAI was transmitted by facsimile on July 8, 2004, to Mr. John Nagle, PSEG Nuclear LLC (the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Office of Nuclear Reactor Regulation (NRR) and to support a conference call with the licensee to discuss the RAI. The RAI was related to the licensees submittal dated March 1, 2004, concerning the utilization of a Risk Informed Inservice Inspection Program. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRR staff position regarding the licensees request.
Docket No. 50-354
Attachment:
Draft RAI
July 13, 2004 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Daniel S. Collins, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC2221)
The attached draft RAI was transmitted by facsimile on July 8, 2004, to Mr. John Nagle, PSEG Nuclear LLC (the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Office of Nuclear Reactor Regulation (NRR) and to support a conference call with the licensee to discuss the RAI. The RAI was related to the licensees submittal dated March 1, 2004, concerning the utilization of a Risk Informed Inservice Inspection Program. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRR staff position regarding the licensees request.
Docket No. 50-354
Attachment:
Draft RAI DISTRIBUTION PUBLIC JClifford DCollins PDI-2 Reading MRubin MMelnicoff MMitchell ZFu GMiller Accession Number: ML041950101 OFFICE PDI-2/PE PDI-2/PM NAME GMiller DCollins DATE 7/8/04 7/8/04
OFFICIAL RECORD COPY DRAFT-REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE TO UTILIZE A RISK INFORMED-INSERVICE INSPECTION PLAN HOPE CREEK GENERATING STATION By letter dated March 1, 2004, PSEG Nuclear, LLC (PSEG) submitted a proposed alternative to the requirements of Rules for Inservice Inspection of Nuclear Power Plant Components,Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the Hope Creek Generating Station (HGCS). The request was submitted pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i). The Nuclear Regulatory Commission staff has been reviewing your submittal and has determined that the following additional information is required to complete our review:
- 1. Regulatory Guide (RG 1.178, An approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping, Revision 1, dated September 2003, replaced the original For Trial Use RG dated September 1998. Revision 1 of RG 1.178 includes guidance on what should be included in risk informed-inservice inspection (RI-ISI) submittals, particularly in dealing with probabilistic risk assessment (PRA) issues. Specifically, on page 28 of RG 1.178, the following is stated:
A description of the staff and industry reviews performed on the PRA.
Limitations, weakness or improvements identified by the reviewers that could change the results of the PRA should be discussed. The resolution of the reviewer comments, or an explanation of the insensitivity of the analysis used to support the submittal to the comment, should be provided.
Section 1.2 of your submittal discussed the HCGS IPE. By letter dated April 23, 1996, the NRC issued a safety evaluation, concluding that the IPE had met the intent of GL88-20, and had identified plant-specific vulnerabilities per the guidance of NUREG-1335.
With regard to the IPE, answers to the following are required:
- a. What weaknesses were identified?
- b. What was done to correct the identified weaknesses or why the uncorrected weaknesses are not relevant to this application?
- 2. In Section 1.2 of your submittal, you identify that an industry peer review was completed in November of 1999. The Section notes that most of the significant findings from this formal peer review were incorporated in Revision 1.3 and that this revision of the PRA model was used in your submittal. Section 1.2 further states that the main comments from the peer review were associated with the treatment of the human action dependencies and the Level 2 Large Early Release Frequency (LERF) sequences timing. While the staff concurs with your expectation that a pessimistic adjustment of
the timing of LERF sequences would not impact the consequence rankings, the following information is needed in regard to the human action:
- a. Was the peer review comment about human action dependencies corrected by Revision 1.3?
- b. If Revision 1.3 did not address the human action dependencies concern (i.e., the dependent Human Error Probabilities (HEPs) are basically unchanged since the peer review), explain why the consequences rankings would likely not be affected by a correction to this issue.
- 3. Section 3.6.1 indicates that you used the Simplified Risk Quantification Method as described in Section 3.7 of the Electric Power Research Institute (EPRI) Topical Report (TR) 112657 in support of your overall risk impact assessment. You selected 1E-08 per weld-year as the pressure boundary failure frequency for a weld with no known degradation mechanism (i.e., low failure potential) and a value of 20 times that (i.e., 2E-07) for a weld with medium failure potential, which is similar to the failure rate used by some of the pilot plants for the EPRI TR, as noted by your citation of References 9 and 14 in the TR.
- a. Given this information, a Category 4 weld should have a contribution to CDF of (1E-03) * (1E-08) or 11E-11/year. Assuming that the inspections are 100 percent effective in finding flaws before they progress to a rupture, then the decrease of one weld inspection should result in an increase in CDF of 1.0E-11/year. Table 3.6-1, which presents the risk impact results, indicates a net decrease of seven system RPV Category 4 weld inspections, resulting in a CDF increase of 3.5E-11/year, rather than the expected 7.0E-11/year. Additionally, Table 3.6-1 lists a net increase of four system BE Category 4 weld inspections, resulting in a CDF decrease of 2.0E-11/year, rather than the expected 4.0E-11/year. Clarify this discrepancy.
- b. Many of the numerical entries in Table 3.6-1 have the same CDF impact or LERF impact values in the w/ [with] POD [probability of detection] column as in the w/o [without] POD column, while other entries have different CDF and LERF impact values between the two columns. Explain why the w/ POD and w/o POD values are sometimes, but not consistently different.
- i. Provide an example calculation of CDF and LERF impact for a Category 4 group of welds in which there is no CDF/LERF impact between the w POD and w/o POD columns.
- 4. Section 2.2 of the submittal lists augmented inspection programs that were considered during the RI-ISI application. Section 6.5 of EPRI TR-112657 also provides a listing of augmented inspection programs, and how they are to be treated in relation to the RI-ISI program. Two programs, applicable to boiling water reactors, are listed in the EPRI document which are not discussed in Section 2.2 of your submittal. Specifically, NRC Bulletin 88-08 (Thermal Stresses in Piping Connected to Reactor Coolant Systems) and NRC Generic Letter 89-13 (Service Water Integrity Program) were identified. Describe how these two augmented inspection programs were treated with respect to the HCGS RI-ISI program.
- 5. As explained in paragraph 4 of Section 3.5, and reiterated in the notes to Table 3.5 of the March 1, 2004 submittal, you have included 6 non-Category A Intergranular Stress Corrosion Cracking (IGSCC)-susceptible welds in the scope of the RI-ISI program. This was done even though you indicated that the IGSCC inspection program was to be unaffected by the RI-ISI program and welds only susceptible to IGSCC are excluded from the RI-ISI program scope such that IGSCC susceptibility was no longer considered in the risk-ranking of a piping segment. Therefore, the scope of piping segments left for consideration under the RI-ISI program include only IGSCC welds susceptible to multiple degradation mechanisms.
Section 3.6.4 of EPRI TR-112657 provides two alternatives for selecting weld locations.
The alternatives are also discussed in ASME Code Cases N-560 and N-578, but the staff has only endorsed the alternatives as described in the EPRI Topical Report and has not endorsed the Code Cases. The selection alternatives discussed in Section 3.6.4.1 and 3.6.4.2 correspond to discussions in ASME Code Case N-560 and N578 respectively. In Section 3.6.4.1 of the TR, there are explicit provisions for crediting an augmented inspection program examination as an RI-ISI examination, provided that the location is a high risk location (Risk Categories 1, 2, or 3), and that no more than half of the total RI-ISI examinations may be borrowed from these programs. Section 3.6.5.1 expands on this discussion by noting that the locations of these borrowed examinations must be identical to those called out in the augmented inspection program, and not one that is within the scope of the program, but not identified for inspection.
Section 3.6.4.2 of the TR requires that the augmented inspection program remain completely as is. All elements in high and medium risk segments that are part of these programs must continue to be examined. The number, location, and frequency would remain the same. These programs are not subsumed into the EPRI RI-ISI program (with the exception of Category A IGSCC welds). The section further states that elements determined to have degradation mechanisms, other than those in the Flow Accelerated Corrosion (FAC) and IGSCC inspection programs are to be included in the RI-ISI program. The number and locations are to be selected according to the RI-ISI program. There is no provision in this section which allows augmented inspections to be credited toward the total number of RI-ISI examinations.
Section 3.6.5.2 of the TR, which discusses the attributes of a Code Case N-578 examination, only reiterates the provisions for welds that are under the jurisdiction of an augmented inspection program. No additional information is given. For welds not under one of these programs, this section provides additional guidance for selection of locations. Again, there is no provision given for crediting these augmented inspection program examinations toward the RI-ISI examination count.
In the first alternative, augmented program elements are fully included in the RI-ISI program but augmented inspections may be credited to satisfy the required number of inspection locations. In the second alternative, augmented program elements (and degradation mechanism) are excluded from the RI-ISI program although discontinued Section XI inspections must still be reflected in the change in risk estimates. There are no provisions in EPRI TR-112657 for mixing the alternatives by excluding the
augmented inspection program elements and degradation mechanism but crediting the inspections.
Section 3.5 of your submittal, and the notes to Table 3.5, appear to indicate that you have excluded all augmented program elements from the RI-ISI program but have credited some of the inspections in the RI-ISI program, in essence, mixing the alternatives. Explain this apparent discrepancy.
- 6. Section 3 of PSEGs March 1, 2004 submittal states that the RI-ISI program for HCGS will deviate from the EPRI RI-ISI methodology for the assessment for thermal stratification, cycling, and striping (TASCS). State whether or not the revised methodology for assessing TASCS potential is in conformance with the updated criteria described in the EPRI letter to the NRC dated March 28, 2001. Also, confirm that as stated in the March 28, 2001 letter (Available under ADAMS Accession Number ML011070238), once the final material reliability program guidance has been developed, the RI-ISI program will be updated for the evaluation susceptibility to TASCS, as appropriate.
- 7. Section 2.2 of the submittal states, in part, [t]he feedwater nozzle-to-safe end weld locations are included in the scope of both the NUREG 0619 Program and the RI-ISI Program. The plant augmented inspection program requirements for these locations are not affected or changed by the RI-ISI Program. Explain if credit has been taken from this augmented program as part of the RI-ISI program. If so, explain the weld selection criteria as compared to EPRI TR-112657, given that NUREG-0619 is not considered as an augmented program in EPRI TR-112657.
- 8. Section 3.5 of the submittal states, in part, [t]he above sampling percentage does not take credit for any inspection locations selected for examination per the plants augmented inspection program for FAC beyond those selected per the RI-ISI process.
It should be noted that no FAC examinations are being credited to satisfy RI-ISI selection requirements. Inspection locations selected for RI-ISI purposes that are in the FAC Program will be subjected to an independent examination to satisfy the RI-ISI Program requirements. Provide information on those selections made by the RI-ISI process that are also included in the augmented FAC program.
- 9. The second paragraph of Section 3.5.1 states that additional examinations will be conducted during the current outage. Clarify the time frame for second sample examinations.